CN116705373A - Irradiation target for producing isotope and isotope production reactor - Google Patents
Irradiation target for producing isotope and isotope production reactor Download PDFInfo
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- CN116705373A CN116705373A CN202310507381.1A CN202310507381A CN116705373A CN 116705373 A CN116705373 A CN 116705373A CN 202310507381 A CN202310507381 A CN 202310507381A CN 116705373 A CN116705373 A CN 116705373A
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- 238000004519 manufacturing process Methods 0.000 title claims abstract description 44
- 239000000446 fuel Substances 0.000 claims abstract description 60
- 239000008188 pellet Substances 0.000 claims abstract description 51
- 238000005253 cladding Methods 0.000 claims abstract description 25
- 230000000712 assembly Effects 0.000 claims abstract description 22
- 238000000429 assembly Methods 0.000 claims abstract description 22
- 230000007246 mechanism Effects 0.000 claims description 12
- 239000003758 nuclear fuel Substances 0.000 claims description 11
- 239000001307 helium Substances 0.000 claims description 5
- 229910052734 helium Inorganic materials 0.000 claims description 5
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims description 5
- 239000002826 coolant Substances 0.000 claims description 4
- 229910000831 Steel Inorganic materials 0.000 claims description 3
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 claims description 3
- 230000000694 effects Effects 0.000 claims description 3
- 239000010959 steel Substances 0.000 claims description 3
- 229910000439 uranium oxide Inorganic materials 0.000 claims description 3
- 230000004992 fission Effects 0.000 description 10
- 230000009257 reactivity Effects 0.000 description 9
- 238000011160 research Methods 0.000 description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 6
- 239000000463 material Substances 0.000 description 5
- 238000000034 method Methods 0.000 description 5
- 239000011148 porous material Substances 0.000 description 4
- 229910052770 Uranium Inorganic materials 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 3
- 238000006243 chemical reaction Methods 0.000 description 3
- 230000004907 flux Effects 0.000 description 3
- 238000009206 nuclear medicine Methods 0.000 description 3
- 238000003860 storage Methods 0.000 description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 3
- 238000013461 design Methods 0.000 description 2
- 230000001678 irradiating effect Effects 0.000 description 2
- 229910052751 metal Inorganic materials 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000001228 spectrum Methods 0.000 description 2
- 239000013077 target material Substances 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 239000011888 foil Substances 0.000 description 1
- 239000012634 fragment Substances 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 230000014509 gene expression Effects 0.000 description 1
- 229910002804 graphite Inorganic materials 0.000 description 1
- 239000010439 graphite Substances 0.000 description 1
- 230000036541 health Effects 0.000 description 1
- 230000001939 inductive effect Effects 0.000 description 1
- 238000005457 optimization Methods 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000007480 spreading Effects 0.000 description 1
- 238000003892 spreading Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
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Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Particle Accelerators (AREA)
Abstract
The application discloses an irradiation target for producing isotopes and an isotope production reactor, wherein the irradiation target comprises an outer cladding, the outer cladding is of a barrel structure, and the barrel structure comprises a plurality of wing channels which are intersected at one point; the plurality of wing channels are arranged at equal intervals by taking the intersection point as the center, and a plurality of target layers are arranged in the plurality of wing channels at equal intervals along the axial direction of the outer cladding; the target layer includes a plurality of irradiation pellets disposed in each of the lanes at equal intervals along a cross-sectional direction of the outer envelope. Based on the irradiation target, the application also provides a reactor, the irradiation target is added between fuel assemblies of the reactor, and a plurality of irradiation pellets are arranged in the irradiation target.
Description
Technical Field
The application relates to the technical field of medical isotope production reactors, in particular to an irradiation target for producing isotopes and an isotope production reactor provided with the irradiation target.
Background
In recent years, nuclear medicine has been rapidly spreading, and the number of nuclear medicine visits has been greatly increased year by year, so that the supply of medical isotopes, which are the basis of nuclear medicine core substances, has been under growing tension. The production of medical isotopes comes mainly from reactors and accelerators. The isotope production by the reactor is mainly neutron irradiation of the target in the irradiation tunnel of the reactor. Compared with the accelerator, the reactor isotope production has the advantages of large yield, high specific activity and the like.
There are two main methods for producing isotopes by irradiation of targets in a reactor. One is to obtain the target isotope from fissile fragments by neutron induced fission of the fissile nuclide (nuclear fuel). The other is to activate the lead nuclide to obtain the target isotope by neutron capture of the lead nuclide. Both methods make use of extremely high neutron flux in the reactor. In contrast, the isotope yield and specific activity of the fission method are relatively high, and the method has medical value.
Although conventional nuclear fuels may also produce target isotopes by fission, the target irradiation period is also short because the half-life of target isotopes is generally short (typically several hours to tens of hours). In such a short irradiation period, the fuel achieves a shallow burnup depth, which would result in fuel wastage if conventional nuclear fuel were used. In addition, the nuclear fuel central region has a high fast neutron flux, which is unfavorable for fission to produce isotopes. The large amount of cracking heat generated by conventional fuels also presents challenges for safe operation of the reactor. Targets for isotope production therefore often require specific designs that are targeted.
Research stacks or experimental stacks available for isotope production worldwide are mostly mainly used for the tasks of material irradiation, neutron beam extraction and the like, and the reserved pore channels available for isotope production are few (or are designed as single pore channels), so that the isotope yield is limited.
Chinese patent CN202111491938.4 discloses a neutron hospital reactor which is specially designed for medical application, the reactor comprises a reactor core placed in a water tank, the water tank is arranged in a water tank, both inside and outside the water tank are light water coolant, the reactor core comprises a fuel component and a control rod, the reactor core is surrounded by a graphite reflecting layer, an operation bridge is arranged at the top of the water tank, a target/fuel component taking and delivering mechanism is arranged on the operation bridge, the target/fuel component taking and delivering mechanism is connected with the reactor core through a target taking and delivering conduit, target irradiation grids are respectively arranged at four corners of the reactor core, and isotope production targets are arranged in the target irradiation grids; the size of the target irradiation grid is consistent with that of the reactor core fuel assembly, each target irradiation grid is divided into four parts uniformly, the cross section of each target irradiation grid is in a shape of a Chinese character 'Tian', and four isotope production targets are arranged in each grid; the fuel assembly is a square column-shaped fuel assembly, and a plate-shaped fuel element is inserted into the fuel assembly.
In the neutron hospital reactor disclosed in the above patent document, 16 targets for isotope production can be arranged in total, although the arrangement number of the targets in the reactor is improved to a certain extent, the used isotope production targets are still traditional cylindrical targets, the targets are loaded at four corners of the periphery of the reactor core, the overall utilization rate of fission neutrons is not high, and the overall isotope production still needs to be improved.
Therefore, the conventional research pile or experimental pile for isotope production has few reserved holes for isotope production, and the neutron utilization rate is low, so that the isotope yield is limited, and a reactor core design specially serving for isotope production is needed to be designed so as to improve the isotope yield and meet the isotope demand in the medical and health field.
Disclosure of Invention
The application provides an irradiation target for isotope production and an isotope production reactor, which are used for solving the problem of low isotope production of the reactor in the prior art.
In order to achieve the above object, the present application provides the following technical solutions:
the application provides an irradiation target for isotope production, which comprises an outer cladding, wherein the outer cladding is of a cylinder structure which is penetrated up and down, and the cylinder structure comprises a plurality of wing channels which are intersected at one point; the wing channels are arranged at equal intervals by taking the intersection point as the center; a plurality of target layers are arranged in the wing channels at equal intervals along the axis direction of the outer shell; the target layer comprises a plurality of irradiation pellets which are arranged in each wing channel at equal intervals along the cross section direction of the outer cladding; helium is filled in the gaps between two adjacent irradiation pellets and between the irradiation pellets and the outer shell;
after the wing channels are intersected, a plurality of short-side wings are formed by taking an intersection point as a center, and a region for arranging a fuel assembly is formed between two adjacent short-side wings; the length of one of the short side wings is less than the radial diameter of the fuel assembly.
In the above technical solution, the cylinder structure includes two wing channels intersecting at a point; the two wing channels are mutually perpendicular to form a cylinder structure with a cross-shaped cross section, and a plurality of target layers are arranged in the two wing channels at equal intervals along the axial direction of the outer casing; the target layer comprises a plurality of irradiation pellets which are arranged in the two wing channels at equal intervals along the cross section direction of the outer cladding; after the two wing channels are intersected, four short-side wings are formed by taking an intersection point as a center, and a fuel assembly is arranged between two adjacent short-side wings.
Further, one of the target layers comprises a plurality of irradiation pellets arranged in a single row at equal intervals in one of the lanes, and a plurality of irradiation pellets arranged in a single row at equal intervals in the other of the lanes; the spacing between two adjacent irradiated pellets in each wing channel is equal.
Further, the interval between two adjacent target layers is equal to the interval between two adjacent irradiation pellets in each wing channel.
Further, the outer cladding is a steel outer cladding; the length of any two short side wings is the same along the cross section direction of the outer cladding.
Further, the irradiation pellets are made of uranium oxide; the irradiated pellets contain nuclear fuel, and the nuclear fuel is U-235 with the concentration less than or equal to 20%.
In another aspect, based on the irradiation target for isotope production provided above, the present application provides an isotope production reactor comprising a core and a core reflection layer surrounding the core periphery; the core includes a central fuel assembly, a plurality of irradiation targets and a plurality of fuel assemblies disposed about a periphery of the central fuel assembly.
In the above technical scheme, a plurality of irradiation targets are uniformly arranged at equal intervals by taking the central fuel assembly as a center, and the irradiation targets and the fuel assembly are arranged at intervals.
Further, after the two wing channels are intersected, four fan-shaped areas with an included angle of 90 degrees are formed, and one fuel assembly is arranged in each fan-shaped area.
Further, after the two wing channels meet, four short-side wings are formed by taking the intersection point as the center, and the length of one short-side wing is smaller than the radial diameter of the fuel assembly.
Further, the axial height of the irradiation target is higher than the height of the active area of the reactor core.
Further, the reactor core is arranged in a reactor pool, coolant is filled in the reactor pool, a target driving mechanism is arranged above the reactor pool, and the target driving mechanism is used for moving the irradiation target up and down, so that the irradiation target is inserted into or pulled out of the reactor core.
Further, one of the irradiation targets corresponds to one of the target drive mechanisms.
Compared with the prior art, the application has the following beneficial effects:
1. the application provides an irradiation target for producing isotopes, which comprises an outer cladding, wherein the outer cladding is of a barrel structure, and the barrel structure comprises at least two wing channels which are intersected at one point; the two wing channels are mutually perpendicular to form a cylinder structure with a cross-shaped cross section, and a plurality of target layers are arranged in the two wing channels at equal intervals along the axial direction of the outer cladding; the target layer comprises a plurality of irradiation pellets which are arranged in the two wing channels at equal intervals along the cross section direction of the outer cladding; the gaps between two adjacent irradiation pellets and between the irradiation pellets and the outer envelope are filled with helium. Therefore, the irradiation target provided by the application is provided with the plurality of irradiation pellets, so that the total storage quantity of nuclear fuel in the irradiation target is increased by the plurality of irradiation pellets, thermal neutrons are more effectively utilized, and the isotope production is increased.
2. The application further provides an isotope production reactor, which comprises a reactor core, a plurality of irradiation targets and a plurality of fuel assemblies, wherein the irradiation targets and the fuel assemblies are arranged around the periphery of the central fuel assembly, the irradiation targets and the fuel assemblies are arranged at intervals, and the interval between any two adjacent irradiation targets is consistent. According to the application, the gap between the fuel assemblies is increased on the basis of the arrangement of the reactor core of the universal research reactor, the irradiation targets with cross sections are arranged between the fuel assemblies, and the interval between the fuel assemblies is increased compared with that of the traditional low-power research reactor using the similar assemblies, so that more moderator is introduced, neutron moderation in the gap between the assemblies is enhanced, and a softer neutron energy spectrum is beneficial to improving the medical isotope yield.
3. In the reactor provided by the application, the irradiation targets with cross-shaped cross sections are arranged between the fuel assemblies, so that the positive reactivity can be provided, the reactor core reactivity can be reduced after the irradiation targets are lifted out of the reactor core, and the irradiation targets and the control rods can participate in reactor core reactivity control together, namely, one more type of reactivity control protection is provided.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present application, the drawings that are needed in the embodiments will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present application, and other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art. It should be understood that the specific shape and configuration shown in the drawings are not generally considered limiting conditions in carrying out the application; for example, those skilled in the art will be able to make routine adjustments or further optimizations for the addition/subtraction/attribution division, specific shapes, positional relationships, connection modes, dimensional proportion relationships, and the like of certain units (components) based on the technical concepts and the exemplary drawings disclosed in the present application.
FIG. 1 is a schematic plan view of an irradiation target for isotope production according to one embodiment of the present application, and further illustrating the positional relationship of the irradiation target with a fuel assembly disposed therearound;
FIG. 2 is a schematic plan view of a partial structure of a reactor core according to one embodiment of the present application;
FIG. 3 is a schematic view showing an arrangement state of multiple target layers in an irradiation target in a horizontal plane according to an embodiment of the present application;
fig. 4 is a schematic view of a multi-layered target layer of an irradiation target according to an embodiment of the present application, which is arranged adjacently above and below a vertical plane.
Reference numerals illustrate:
1. an outer envelope; 2. irradiating the pellets; 3. a fuel assembly; 4. irradiating the target; 5. a moderator flow passage; 6. a target layer; 7. a wing lane; 8. a central fuel assembly.
Detailed Description
The application will be further described in detail by means of specific embodiments with reference to the accompanying drawings.
In the description of the present application: unless otherwise indicated, the meaning of "a plurality" is two or more. The terms "first," "second," "third," and the like in this disclosure are intended to distinguish between the referenced objects without a special meaning in terms of technical connotation (e.g., should not be construed as emphasis on the degree of importance or order, etc.). The expressions "comprising", "including", "having", etc. also mean "not limited to" (certain units, components, materials, steps, etc.).
The terms such as "upper", "lower", "left", "right", "middle", etc. are generally used herein for convenience of visual understanding with reference to the drawings and are not to be construed as absolute limitations on the positional relationship of the actual product. Such changes in the relative positional relationship without departing from the technical idea of the present application are also considered as the scope of the present application.
Example 1
The existing irradiation reactor is mainly used for material irradiation, the arrangement quantity of irradiation targets in a reactor core in the reactor for material irradiation is limited, and in addition, the targets are metal foils in irradiation pore channels, so that the metal uranium loading quantity is low, and the isotope yield is low.
In order to solve the problems in the prior art, the application provides an irradiation target for producing isotopes and an isotope production reactor, wherein the irradiation target is inserted into an irradiation pore canal in the reactor, and the irradiation target initiates nuclear fission reaction of a target material by utilizing a high neutron flux field in the reactor, so that the target isotopes are separated and extracted from fission products. The reactor core target capacity of the reactor provided by the application is larger, so that the isotope yield can be improved, and the economy is improved.
The following describes in detail the structure of an irradiation target for isotope production provided in this embodiment:
the embodiment provides an irradiation target for isotope production, referring to fig. 1, the irradiation target comprises an outer cladding 1, wherein the outer cladding 1 is of a cylinder structure which is penetrated up and down, and the cylinder structure comprises two wing channels 7 which are intersected at one point; the two wing channels 7 are mutually perpendicular to form a cylinder structure with a cross-shaped cross section, and a plurality of target layers 6 are arranged in the two wing channels 7 at equal intervals along the axial direction of the outer casing 1; the target layer 6 comprises a plurality of irradiation pellets 2 which are arranged in two wing channels 7 at equal intervals along the cross section direction of the outer envelope 1; the gaps between two adjacent irradiation pellets 2 and between the irradiation pellets 2 and the outer envelope 1 form a moderator flow passage 5, and helium is filled in the moderator flow passage 5. That is, a micro gap is left between the outer cladding and the irradiation pellet, which can be used for cladding fission products such as fission gas and the like, and margin is left for irradiation expansion of the target material. The micro gap is filled with helium which can act to enhance heat transfer between the pellets and the inner envelope.
In the irradiation target, the intersection point is taken as the center, and the two wing channels form four fan-shaped areas with an included angle of 90 degrees, and the fan-shaped areas are used for installing the fuel assembly. Referring to fig. 3 and 4, one target layer includes a plurality of irradiation pellets in a single row equally spaced in one lane and a plurality of irradiation pellets in a single row equally spaced in the other lane. The spacing between two adjacent irradiated pellets in each wing channel is equal. Further, the spacing between two adjacent target layers is equal to the spacing between two adjacent irradiated pellets in each wing. The arrangement rule is mainly to keep the interval between two adjacent irradiation pellets in space, namely, the two adjacent irradiation pellets are all consistent, and the local hot spot can be avoided in the irradiation process.
The outer cladding of the irradiation target provided by the embodiment is a steel outer cladding. The material of the irradiation pellets can be uranium oxide. The irradiated pellets contain nuclear fuel which is U-235 with the concentration less than or equal to 20 percent.
In a specific arrangement example, a plurality of irradiation pellets may be arranged in the target outer envelope having the cross-shaped cross-section, in particular, 9 irradiation pellets may be arranged along the cross-section direction (i.e., on the horizontal plane) of the outer envelope, 45 target layers may be arranged in total along the axial direction (i.e., the vertical direction) of the outer envelope, and the outer envelope is loaded with 9×45=405 irradiation pellets in total.
The irradiation pellets for isotope production are arranged in the outer casing of the target with the cross-shaped cross section, the outer casing is better than a basket with a plurality of pellets, the number of the irradiation pellets is more than the total storage amount of nuclear fuel in the natural target, thermal neutrons can be more effectively utilized in the reaction, and the isotope yield is improved, so that the problem of low isotope yield in a general research pile or an experimental pile is solved.
Example two
In accordance with the irradiation target for isotope production provided in the first embodiment, the present embodiment provides an isotope production reactor including a core and a core reflection layer surrounding the core; referring to fig. 2, the core includes a central fuel assembly 8, a plurality of irradiation targets 4 and a plurality of fuel assemblies 3 disposed about the periphery of the central fuel assembly 8. The axial height of the irradiation target is higher than the height of the active region of the reactor core. The reactor core is arranged in a reactor pool, coolant is filled in the reactor pool, a target driving mechanism is arranged above the reactor pool, and the target driving mechanism is used for moving the irradiation target up and down, so that the irradiation target is inserted into or pulled out of the reactor core. When the target is replaced, the irradiation target can be lifted upwards by the target driving mechanism. One irradiation target corresponds to one target driving mechanism, and each irradiation target is provided with an independent driving device so as to be independently adjusted or replaced.
The irradiation targets provided in the first embodiment are installed in a reactor core, a plurality of irradiation targets are uniformly arranged at equal intervals by taking a central fuel assembly as a center, the irradiation targets and the fuel assembly are arranged at intervals, and the interval between any two adjacent irradiation targets is consistent; after the two wing channels are intersected, four fan-shaped areas with an included angle of 90 degrees are formed, and each fan-shaped area is provided with a fuel assembly; after the two wing channels are intersected, four short-side wings are formed by taking an intersection point as a center, and the length of one short-side wing is smaller than the radial diameter of the fuel assembly so as to prevent the irradiation target from being blocked when moving.
Referring to fig. 2, 12 irradiation targets 4 are disposed in the illustrated reactor core.
The fuel assemblies in the reactor provided by the application are the same as the universal fuel assemblies of the low-power research reactor, the square fuel assemblies are still selected as the inherent assemblies of the reactor core, and the square fuel assemblies are formed by fuel plates. In the reactor provided by the application, the distance between the fuel assemblies is increased compared with that of a traditional low-power research reactor using similar assemblies, so that more moderator is introduced, and neutron moderation in the assembly gaps is enhanced. The softer neutron spectrum is beneficial to improving the yield of medical isotopes.
Irradiation targets with cross-shaped cross sections can be distributed at multiple positions in the reactor core. The cross-section is cross-shaped, and the irradiation target is provided with a very small irradiation pellet, and the irradiation pellet contains low-concentration uranium (U-235 concentration is less than or equal to 20%). The main medical isotopes, such as Mo-99 and I-131, are obtained by inducing fission reactions by neutron irradiation U-235 in the reactor. The irradiation target with cross-shaped cross section can be lifted or inserted into the reactor core under the drive of the target driving mechanism, so that the target can be flexibly replaced or the reactor reactivity can be controlled in an emergency state.
According to the application, the irradiation target with cross-shaped cross section is added between the fuel assemblies, and the isotope production pellets (namely irradiation pellets) are arranged in the irradiation target, so that the storage amount of uranium fuel in the target can be increased, and the problem of low isotope yield in a general research pile or an experimental pile is solved.
In the reactor provided by the application, the irradiation targets with cross-shaped cross sections are arranged between the fuel assemblies, so that the positive reactivity can be provided, the reactor core reactivity can be reduced after the irradiation targets are lifted out of the reactor core, and the irradiation targets and the control rods can participate in reactor core reactivity control together, namely, one more type of reactivity control protection is provided.
Any combination of the technical features of the above embodiments may be performed (as long as there is no contradiction between the combination of the technical features), and for brevity of description, all of the possible combinations of the technical features of the above embodiments are not described; these examples, which are not explicitly written, should also be considered as being within the scope of the present description.
The application has been described above with particularity and detail in connection with general description and specific embodiments. It should be understood that numerous conventional modifications and further innovations may be made to these specific embodiments, based on the technical concepts of the present application; but these conventional modifications and further innovations may also fall within the scope of the claims of the present application as long as they do not depart from the technical spirit of the present application.
Claims (8)
1. The irradiation target for isotope production is characterized by comprising an outer cladding, wherein the outer cladding is of a cylinder structure which is penetrated up and down, and the cylinder structure comprises a plurality of wing channels which are intersected at one point; the wing channels are arranged at equal intervals by taking the intersection point as the center; a plurality of target layers are arranged in the wing channels at equal intervals along the axis direction of the outer shell; the target layer comprises a plurality of irradiation pellets which are arranged in each wing channel at equal intervals along the cross section direction of the outer cladding; helium is filled in the gaps between two adjacent irradiation pellets and between the irradiation pellets and the outer shell;
after the wing channels are intersected, a plurality of short-side wings are formed by taking an intersection point as a center, and a region for arranging a fuel assembly is formed between two adjacent short-side wings; the length of one of the short side wings is less than the radial diameter of the fuel assembly.
2. The irradiation target for isotope production of claim 1 wherein said barrel structure includes two wings meeting at a point; the two wing channels are mutually perpendicular to form a cylinder structure with a cross-shaped cross section, and a plurality of target layers are arranged in the two wing channels at equal intervals along the axial direction of the outer casing; the target layer comprises a plurality of irradiation pellets which are arranged in the two wing channels at equal intervals along the cross section direction of the outer cladding;
after the two wing channels are intersected, four short-side wings are formed by taking an intersection point as a center, and a fuel assembly is arranged between two adjacent short-side wings.
3. The irradiation target for isotope production of claim 1 wherein one of said target layers comprises a single row of equally spaced plurality of irradiation pellets in one of said lanes and a single row of equally spaced plurality of irradiation pellets in the other of said lanes; the interval between two adjacent irradiation pellets in each wing channel is equal;
the spacing between two adjacent target layers is equal to the spacing between two adjacent irradiated pellets in each wing channel.
4. The irradiation target for isotope production of claim 1 wherein the outer envelope is a steel outer envelope; the length of any two short side wings is the same along the cross section direction of the outer cladding.
5. The irradiation target for isotope production of claim 1 wherein the irradiation pellets are uranium oxide;
the irradiated pellets contain nuclear fuel, and the nuclear fuel is U-235 with the concentration less than or equal to 20%.
6. An isotope production reactor comprising an irradiation target for producing isotopes according to any one of claims 1-5; the isotope production reactor comprises a reactor core and a reactor core reflecting layer surrounding the periphery of the reactor core; the core includes a central fuel assembly, a plurality of irradiation targets and a plurality of fuel assemblies disposed about a periphery of the central fuel assembly.
7. The isotope production reactor of claim 6, wherein a plurality of said irradiation targets are uniformly disposed in a plurality of turns equally spaced about said central fuel assembly, said irradiation targets being spaced from said fuel assembly;
after the two wing channels are intersected, four fan-shaped areas with an included angle of 90 degrees are formed, and each fan-shaped area is provided with one fuel assembly;
after the two wing channels are intersected, four short-side wings are formed by taking an intersection point as a center, and the length of one short-side wing is smaller than the radial diameter of the fuel assembly;
the axial height of the irradiation target is higher than the height of the active area of the reactor core.
8. The isotope production reactor of claim 7, wherein the reactor core is disposed in a reactor pool filled with coolant, a target drive mechanism is disposed above the reactor pool to effect up and down movement of the irradiation targets such that the irradiation targets are inserted into or withdrawn from the reactor core;
one of the irradiation targets corresponds to one of the target drive mechanisms.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310507381.1A CN116705373A (en) | 2023-05-06 | 2023-05-06 | Irradiation target for producing isotope and isotope production reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310507381.1A CN116705373A (en) | 2023-05-06 | 2023-05-06 | Irradiation target for producing isotope and isotope production reactor |
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| Publication Number | Publication Date |
|---|---|
| CN116705373A true CN116705373A (en) | 2023-09-05 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202310507381.1A Pending CN116705373A (en) | 2023-05-06 | 2023-05-06 | Irradiation target for producing isotope and isotope production reactor |
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| Country | Link |
|---|---|
| CN (1) | CN116705373A (en) |
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- 2023-05-06 CN CN202310507381.1A patent/CN116705373A/en active Pending
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